ML19320A227

Tech Spec Change Request for Tech Specs 4.2 Re Removal of Surveillance Specimens for Balance of Cycle 1 Operation & Reinsertion Prior to Cycle 2

ML19320A227
Person / Time
Site:	Arkansas Nuclear
Issue date:	05/20/1976
From:	Phillips J ARKANSAS POWER & LIGHT CO.
To:
References
NUDOCS 8004210526
Download: ML19320A227 (2)

Text

.

fJ;gCs Onm 105 U.S. NUCU. An HECULA T On"OMM10310N DOCF.CT NUMnt:H u.res an_717 NRC DISTRIBUTION rOn PART 50 DOCKET MATERIAL 1TO:

D.L. Ziemann Fl(OM: Arkansas Power & Ligth Co.

DATE OF DOCUMENT Little Rock, Arkansas 5-19-76

)

2..

J.D. Phillips OATE nECEivEO 5-20-76 lDlLETTER

.C NO TO RIZ E O PROP INPUT FORM NUMUEn OF COPIES RECEIVED l

DonlGINAL O UNC LASSIF 4 E O

['

QCOPy 1

'L fi'?"981 the following.......

f 6 ?S$8Ec. Change Request, regarding the remov-C l

al of the surveillance specimens for the balance of cycle I operation and.requirres their reinser-tion prior t6 Cyc M II.......

~

(1 Twix Cy. Received)

\\

' ACKNOWLEDGED N.

• ~

DO NOT Rm..fo y 3 m

J I PLANT NAME:

Arkansas # 1 p&

q g

.b o

o Ju.

SAFETY FOR ACTION /INFOR?.!ATIO.J Eh?IRO 5AB b-25-/6 l ASSIGMED AD :

ASSIG::ED AD :

MRANCH CHIEF :

i t.1emann W / 6 BRANCH CHIEF :

FROJECT ::ANAGER:

PROJECT MANAGER :

v4C. ASST. :

vi995 LIC. ASST. :

INTERNAL DISTRIEUTION d PG FILE)

Sy_$ d 3_gApg7y l pian 7 gyg7 peg

.mn et rn v

'- ' NRC PDR HETNEMAN l Tmvsco ERNST WI & E (111 SCHRnEnr3 BENAROYA BALT,ARD

• ' OELD LAIT lLS SPANGLER COSSICK & STAFF ENGINEERIITG IPPCLITO M,IPC MACCARy SITE TET:ll CASE KNIGHT OPERATING REACTORS GADtILL Ik%AUER SIINEIL STELLO STEPP

!LuLEss PAWLICKI HUU!AN OPERATI?!G TECH PROJECT MANAGEMEhT REACTOR SAFETY

-T'ISENI!UT SITE ANALYSIS BOYD ROSS Wi!AO VOLD:ER P. COLLINS NCVAK ll0USTON WAER BUNCH R0_SZTOCZY

• CIR))R!CI:R

- h-COLLINS 1lETE,RSON Cl!ECK M IMES KREGER MM_LTZ IIELTEMMS AT & I SITE SAFETY & UNVIRC i

SKOVHOLT SAT.TZMAN A?IALYSIS lillTI5E'!U',

MhTn ! A MITT.T. Eft I

EX I Elt!J AL DI:;l lllHU TION CONTitOL NU?.tBEli

' I.I'DR : Deicenilvillo n,.

IfATL 1.AB

!!ROOKilAV,EN llATL LAli it

--T IC REG. V-IE ULRIKSON(URNL)

. LS-diC li.EPDR_

5125 i

ASr.n CONsur.TANTS ROO4'

& dens /GP.~ ec/Sigt 10 g f g

c

• t F.-

gt - #

iW

, e QQ _,~. _ y d,QtE., f*O 'j; k.Vi

~

r&m'gyjkk"&&. p f

G

%e 4.c.

%p.. %

~

_ e.v.

~

p.,15-261 lten Component Excention 6.4 Rolting 20 Not Applicab]

l 6.6 Integrally h'elded Not Applicabl Yalve Supports i

4.2.3

%e structural integrity of the reactor coolant system bout '

shall be r,aintained at the level required by the original tance andards throughout the life of the station. Any e-(j as a result of the tests outlined in Tabic IS-261 of Sectic i

of the code, that defects have developed or grown, shall bt j

investigated.

i 4.2.4-To assure the structural integrity of the reactor internals l out the life of the unit, the two sets of nain internals bc t

I (connecting the core barrel to the core support shield and lower grid cylinder) shall remain in place and under tensio will be verified by visual inspection to determine that the bolt loc. king caps remain in place. All locking caps will b cd after hot functional testing and whenever the internals renoved from the vessel during a refueling or naintenance a The cote barrel to core support shield caps will be inspect refueling shutdown.

4.2.5 Sufficient records of each inspection shall be kept p

to allo, comparison and evaluation of future inspections, 4.2.6

~

a y

Cowpicte surface and volte::ctric examination of the reactor t p cp flywheels will be conducted coincident with refueling 1 naintenance shutdowns such that within a 10 year period aft:

i.

up all four reactor coolant ptmp flywheels will be exanined.

i 4.2.7 Reactor vessel spccinens shall be removed and examined, to d eine changes in caterial properties, at specinen exposures (

equivalent to 3, 9.5,16 and 22.5 Effective Full Power Years

-l of operation.

his withdrawal schedule may be modified to c j

with those refueling outages or plant shutdowns, when the re head is renoved, nost closely approaching the withdrawal sch Results of these exaninations shall be used to update Techni l

Specification 3.1.2.

Specirsens not subjected to destrt.ctivo testing after the first 0.93 EFpY of Cycle 1 asy be removed stored during the renainder of Cycle 1, but shall be re-inst.

y prior to (.'ycle 2.

1 RaSn I

%e surveillance progran has been developed to couply with Section XI

• ASMI: Boller and Pressurc Vessel Code Inservice Inspection of Nuclear Rf Coolant Systens. 1971. including 1971 Winter Addenda Edition p

l De ntu:ber of reactor vessel specimens and the frequencies for renovin; f'

and testing these spccicens are provided to assure compliance with the requirements of Appendix 11 to 10CFR Part 50.

D *

• Q 7# D OT Y

.,g p }, 4 U )]

. h ' p

\\

1

...s e

- = _

.